ML19274C770

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Forwards Response to 781004-05 Telephoned NRC Request for Addl Info Re Facil Defueling
ML19274C770
Person / Time
Site: 07002623
Issue date: 10/20/1978
From: Parker W
DUKE POWER CO.
To: Casey Smith
NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS)
References
NUDOCS 7811170309
Download: ML19274C770 (8)
v • d • e


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DUKE POWER COSIPANY Powza Detsniwo 4cc Sourn Cnuncu STarzT, CE[EEo$, N. C.2e242 i

f October-g (19,78s F.'.1 3 51 wiwau o. pAnnensa.

Vier PmEstORNT TELE Pr*ON E:AmEA 704 STEane Pmoouctrom 373-4093 i

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- $1 Dr. Clifford V. Smith, Jr., Director Office of Nuclear Mater!-l Cafety and Safeguard.

U. S. Lclear Regulatory Commission

~ washington, D. C.

20555

[/

Attention:

Mr. Brett Spitalny Fuel Reprocessing and Recycle Branch DOCXETQ U3..RO OCT 2 61978 >

42.

Subj ect: McGuire Nuclear Station NM55 Docket Number 70-2623 MAttSEGON

/.

DOCKET CLER;<

/

Amendment to SNML-1773 C9 4

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Dear Sir:

Please find attached our response to the request for information you made to members of our staff during telephone conversations of October 4 and 5, 1978, ytrulyyours,,b V

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/N w. e.__ LS. %

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William O. Parker, Jr.

GJP:scs IHis DOCUMENT CONTAlHS Attachments POOR QUAUTY PAGES 7mp

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ATTACHMENT 1 1)

Give dates of initial operation at Oconee.

Include the dates when defueling was necessary for other than a scheduled refueling and the circumstances of this defueling.

RESPONSE

Unit Initial Criticality Dates Commercial Operation Dates Oconee 1 04-19-73 07-16-73 Oconee 2 11-11-73 09-09-74 Oconee 3 69-05-74 12-16-74 During 1976 a problen with the specimen holder tubes at the Oconee type plants developed and required defueling in orde-to perform repairs.

These repairs were made at Oconee, Units 2 and 3 during longer than normal refueling periods.

A special outage was needed on Oconee, Unit I to make the repair. The three daten for the repairs were:

Oconee 1 18-76 Oconee 2 07-76 Oconee 3 18-76 J snee 2 was defueled in February,1974 to retrieve a loose part.

2)

Give the status of Catawba, including projected milestone dates.

RESPONSE

Percent completion:

Catawba Unit 1 - 55%

Catawba Unit 2 - 40%

Milestone dates:

llI][

Fuel Loading Commercial Operation Unit 1 7-80 2-81 7-81 Unit 2 6-82 8-82 1-83

~

3)

Describe the tool and method used in handling the Oconee spent fuel spacer used in the McGuire storage racks.

RESPONSE

The tool used to handle the fuel spacer consists of a square plate slightly less than 5 inches on a side connected to a long handle.

The plate of the tool is

.lcwered through the 5 inch square hole in the spacer, turned 45 degrees, and t'ae spacer lifted.

ith 4)

State North Carolina, South Carolina, county and/or city requirenent:

regard to weight limits for trucks.

Include whether the cask and trailer to ship Oconee fuel to McGuire will be within all cpplicable requirements.

RESPONSE

The gross vehicle weight limits for North Carolina and South Carolina is 80,000 The maximum gross weight of the vehicles transporting the spent fuel from lbs.

Oconee to McGuire will be less than 80,000 lbs.

Provide nn amendment to the present SNM license request to indicate that a 5) total of 354 spent fuel assemblies will be shipped from Oconee to McGuire Unit 1.

Include the accident analysis for loss of pool cooling.

RESPONSE

The total number of spent fuel assemblies to be shipped from Oconee to McGuire has not been determined.

If more than 300 are to be shipped, the spent fuel cooling analysis will be verified to remain valid and any nec-essary license amendments requested.

6)

Indicate any alternate shipping route from that as originally provided.

RESPONSE 1 The primary or preferred route for transporting the fuel from Oconee to McGuire Nuclear Station is as follows:

from Oconee Nuclear Station south on S. C. Route 130 to U. S. 123 and U. S. 76 cast on U. S. 123 to S. C. 153 right (east) on S. C. 153 to Interstate 85 north on I-85 to-I-77 in North Carolina north on I-77 to N. C. Route 73 west on 73 to McGuire Nuclear Station.

The return route is the reverse of the above. A secondary route using U. S.

123 and S. C. 153 from Route 130 to I-85 may be used.

76 instead of U. S.

7) Determine the average population density per square nile along the entire proposed shipping route.

RESPONSE

Tabulated below is our best estimate of the average population densities within the area one-half mile either side of the proposed transport route:

1970 Estimate 1978 Estimate

  • Arca (Persons /sq. mi.)

(Persons /sq. mi.)

McGuire 50 Mile Radius 406 425 Oconee 50 Mile Radius 327 343 Other 347 364 Total Route 369 387

  • Assumed a conservative 5% increase in 1970 population.

It should be noted that the basic assumption used in determining densities is that the population is equally spaced over the area considered.

For large areas (regions, counties, states), this assumption is reasonable. However, for small corridors along major highways, other more time-consuming methods provide more realistic estimates. The above estimates are considered conservatively high.

8) Provide Duke's experience with failed fuel o.seaolies at Oconee; include the-number of F. A.'s involved, the percentage of leaking fuel pins per fuel assembly and a description of the method used to determine / define a leaker.

RESPONSE

The three units at Oconee have experienced various degrees of failed fuel with an average of approximately.09% failed fuel for the stntion. Three methods are used to determine failed fuel rods:

1) Radiochemistry analysis of the reactor coolant
2) Sipping
3) Visual Inspection The radiochemistry analysis method provides the first indication of failed fuel pins and h.is also provided the largest data base of failed fuel. The amount of 1-131 is measured in the reactor coolant and converted to percent failed fuel pins using:

3.2 pCi/ml = 1% defective fuel pins. Past experience indicates an average of 0.089 pCi/ml reactor coolant activity of I-131 which converts to a failure of about 33 fuel rods out of 36816/ core (208 Fuel Rods / Fuel Assembly with 177 Fuel Assemblics/ core) and results in 0.09% failed fuel.

Generally, the sipping and visual inspection methods have been used at Oconee to confirm suspected failed fuel assemblies. Confirned failed fuel will not be shipped to McGuire.

9) Provide a spent fuel transfer schedule.

4%

s

RESPONSE

Refer to Attachment 9A.

10) Provide expected dose accumulations which cculd be expected for:

a)

Shipping 354 spent fuel assemblies from Oconee to McGuire (not reracking the Oconee 1 and 2 spent fuel pool).

b)

Shipping 253 spent fuel assemblies from Oconee to McGuire and reracking the Oconee 1 and 2 spent fuel pool.

RESPONSE

There are three alternatives to be considered:

a)

Shipping 354 spent fuel assemblies from Oconee to McGuire (not reracking the Oconee 1-and 2 spent fuel pool).

Approximately 0.4 Man-Rem / shipment would be experienced.

This results in a total estimated dose for 354 FA's of approximately 140 Man Rem.

b) Reracking the Oconee 1 and 2 spent fuel pool only, results in a total estimated dose accumulation of approxinately 150 Man Rem.

c)

Shipping 253 spent fuel assemblies from Oconee to McGuire and reracking the Oconee 1 and 2 spent fuel pool.

Using 0.4 Man-Rem / shipment results in approximately 100 Man Rem for shipment and 150 Man Rem for reracking, for a total estimated dose of 250 Bbn Rem.

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